Search results for "WCLL"

showing 7 items of 37 documents

Preliminary thermal optimization and investigation of the overall structural behaviour of the EU-DEMO water-cooled lead lithium left outboard blanket…

2022

The conceptual design phase of the EU-DEMO reactor has been recently launched, with the aim of evolving the DEMO pre-conceptual layout towards a more robust and articulated geometric configuration able to cope with most of the design requirements and to show further margins for the passing of the current potential show-stoppers. Hence, the achievement of the conceptual design of the Water-Cooled Lead Lithium Breeding Blanket (WCLL BB) is one of the milestones the EUROfusion consortium aims to achieve in the close future. To this purpose, within the framework of the research activities promoted by EUROfusion, a research campaign has been launched at the University of Palermo, in close cooper…

ThermomechanicsLateral outboardNuclear Energy and EngineeringMechanical EngineeringDWTs optimizationFEM analysisGeneral Materials ScienceBreeding blanketSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringWCLL
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Water Cooled First Wall optimization for WCLL DEMO reactor

2013

WCLL blanketDEMOSettore ING-IND/19 - Impianti NucleariFW
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Optimization of the first wall for the DEMO water cooled lithium lead blanket

2015

The maximum heat load capacity of a DEMO First Wall (FW) of reasonable cost may impact the decision of the implementation of limiters in DEMO. An estimate of the engineering limit of the FW heat load capacity is an essential input for this decision. This paper describes the work performed to optimize the FW of the Water Cooled Lithium-Lead (WCLL) blanket concept for DEMO fusion reactor in order to increase its maximum heat load capacity. The optimization is based on the use of water at typical Pressurised Water Reactors conditions as coolant. The present WCLL FW with a waved plasma-faced surface and with circular channels was studied and the heat load limit has been predicted with FEM analy…

Work (thermodynamics)DesignMaterials scienceMechanical EngineeringNuclear engineeringDesign;DEMO;Blanket;WCLL;First WallFusion powerBlanketFinite element methodWCLLCoolantDesign for manufacturability[SPI]Engineering Sciences [physics]First WallDEMO Blanket WCLL Design First WallNuclear Energy and EngineeringThermalLimiterBlanketGeneral Materials ScienceDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response

2019

Abstract In the framework of EUROfusion Work Package International Cooperation R&D activities, a close collaboration has been started among University of Palermo, ENEA Brasimone and ENEA Frascati for the development of the Water Cooled Lithium Lead (WCLL) Breeding Blanket (BB) concept. In this context, a research campaign has been carried out at the University of Palermo in order to investigate the influence of First Wall (FW) cooling water configuration on the nuclear response of the WCLL BB under irradiation in EU-DEMO, in order to gain useful indications for the WCLL BB pre-conceptual designs. To this end, three-dimensional nuclear analyses have been performed by MCNP5 v. 1.6 Monte Carlo…

Work packageNuclear engineeringNeutronicchemistry.chemical_elementContext (language use)DEMO reactorBlanket7. Clean energy01 natural sciences010305 fluids & plasmas0103 physical sciencesWater coolingNeutronicsDEMO reactor; Neutronics; WCLL blanketGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringParametric statisticsbusiness.industryMechanical EngineeringWater cooledNuclear powerWCLL blanketNuclear Energy and EngineeringchemistryEnvironmental scienceLithiumbusiness
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Advancements in DEMO WCLL breeding blanket design and integration

2018

The water-cooled lithium-lead breeding blanket is a candidate option for the European Demonstration Power Plant (DEMO) nuclear fusion reactor. This breeding blanket concept relies on the liquid lithium-lead as breeder-multiplier, pressurized water as coolant, and EUROFER as structural material. The current design is based on DEMO 2015 specifications and represents the follow-up of the design developed in 2015. The single-module-segment approach is employed. This is constituted by a basic geometry repeated along the poloidal direction. The power is removed by means of radial-toroidal (i.e., horizontal) water cooling tubes in the breeding zone. The lithium-lead flows in a radial-poloidal dire…

breeding blanketbreeding blanket DEMO WCLLbreeding blanket; DEMO; WCLLDEMOSettore ING-IND/19 - Impianti NucleariWCLL
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Development and application of multiscale procedures for the thermomechanical analysis of the DEMO Water-Cooled Lithium Lead Breeding Blanket

2022

The Breeding Blanket is an essential component of the DEMO fusion reactor and its design is one of the pivotal purposes of the DEMO project. Indeed, this component has to withstand severe operating conditions, as it is directly exposed to the plasma, making its design particularly challenging. In particular, the Water-Cooled Lithium-Lead (WCLL) BB concept is one of the candidates currently considered for the conceptual design of the European DEMO reactor. The development of a robust BB system is crucial for the design of the whole DEMO reactor and the thermo-mechanical assessment of the whole BB segments is mandatory to allow checking their structural performances in different loading scena…

breeding blankets thermo-mechanics analysis procedureFEM analysisSettore ING-IND/19 - Impianti NucleariWCLL
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Structural assessment of the EU-DEMO WCLL Central Outboard Blanket segment under normal and off-normal operating conditions

2021

Abstract Within the framework of the EUROfusion design activities concerning the EU-DEMO Breeding Blanket (BB) system, a research campaign has been carried out at the University of Palermo with the aim of investigating the structural behaviour of the DEMO Water-Cooled Lithium Lead (WCLL) Central Outboard Blanket (COB) segment. The assessment has been performed considering three different loading scenarios: the Normal Operation (NO), the Over-Pressurization (OP) and the Upward Vertical Displacement Event (VDE-up). In particular, NO scenario represents the loading case referring to the nominal operating conditions, whereas the OP scenario refers to the loading conditions due to an in-box LOCA…

business.industryDesign activitiesMechanical EngineeringFEM analysisStructural engineeringVDEBlanketPlasma volumeVertical motionFinite element methodWCLLNuclear Energy and EngineeringPlasma chamberGeneral Materials ScienceVertical displacementBreeding blanketbusinessDEMOGeologySettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringEvent (probability theory)
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